Nukleær Sikkerhet og Pålitelighet
2011 - Comparison of in-reactor creep and stress relaxation of cold worked 316 and solution annealed 304L stainless steels in thermal and fast neutron spectrum reactors
Foster, J.,
Karlsen, T.,
last modified
Jan 06, 2012 12:24 PM
2011 - Experimental investigation of irradiation creep and growth of recrystallized Zircaloy-4 guide tubes pre-irradiated in PWR
McGrath, M.,
Yagnik, S.,
last modified
May 31, 2011 01:12 PM
2011 - Experimental investigation of irradiation creep and growth of recrystallized Zircaloy-4 guide tubes pre-irradiated in PWR
Schwartz, J.,
Fandeur, O.,
Rey, C. ,
McGrath, M.A.,
Yagnik, S.,
last modified
Mar 29, 2012 10:25 AM
2011 - Feasibility of performing pool-side fission gas release measurements on fuel rods with short decay time
Holcombe, S.,
Svärd, S.J.,
Eitrheim, K.,
Willman, C.,
Hallstadius, L.,
Reparaz, A.,
last modified
Dec 09, 2011 12:34 PM
2011 - Innovative fuel development in Ulba (Kazakhstan) and testing in the Halden reactor
Russin, Y.,
Shakhvorostov, Y.,
McGrath, M.,
Gagarin, A.,
Volkov, B.,
Kuchkovsky, A.,
last modified
May 15, 2012 09:50 AM
2011 - Instrument capabilities and developments at the Halden reactor project
Solstad, S.,
Van Nieuwenhove, R.,
last modified
May 30, 2011 10:05 AM
2011 - Recommendations for the conditioning of spent metallic uramium fuel and aluminium clad fuel for interim storage and disposal
Bennett, P.,
last modified
Jan 05, 2012 02:52 PM
2011 - Review of instrumentation for irradiation testing of nuclear fuels and materials
Bong Goo, K.,
Rempe, J.L.,
Villard, J.-F.,
Solstad, S.,
last modified
Dec 06, 2011 10:38 AM
2011 - Role of Halden Reactor Project for world-wide nuclear energy development
McGrath, M.A.,
Volkov, B.,
last modified
Jan 06, 2012 12:31 PM
2011 - Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code
Khvostov, G.,
Wiesenack, W.,
Zimmermann, M.A.,
Ledergerber, G. ,
last modified
May 30, 2011 12:04 PM
2011 - Upgrading of the Halden Reactor experimental capabilities for innovative fuel and material testing
Volkov, B. ,
Minagawa, Y.,
Elisenberg, T.,
McGrath, M.,
last modified
Jan 06, 2012 12:39 PM
2010 - Application of research reactors to irradiation testing of nuclear fuels and materials
Wiesenack, W.,
last modified
May 10, 2011 03:16 PM
2010 - Behavior of homogeneous and heterogeneous MOX fuel
Tverberg, T.,
Wiesenack, W.,
Yagnik, S.K.,
Rossiter, G.,
last modified
Aug 29, 2011 04:11 PM
2010 - Changes of the surface-to-volume ratio and diffusion coefficient of fission gas in fuel pellets during irradiation
Amaya, M.,
Grismanovs, V.,
Tverberg, T.,
last modified
Feb 02, 2011 01:53 PM
2010 - Comparative study of inert matrix fuel concepts from IFA-652 experiment
Calabrese, R.,
Vettraino, F.,
Tverberg, T.,
last modified
Feb 02, 2011 01:52 PM
2010 - Crud formation on low duty PWR fuel in the Halden Reactor
Bennett, P.,
last modified
Feb 02, 2011 01:53 PM
2010 - FUMEX-III: A new IAEA coordinated research project on fuel modelling at extended burnup
Killeen, J.,
Sartori, E.,
Tverberg, T.,
last modified
Feb 02, 2011 01:53 PM
2010 - Fuel behaviour modelling - basic principles and related data
Wiesenack, W.,
last modified
Feb 02, 2011 01:52 PM
2010 - Fuel performance beyond design - Exploring the limits
Ledergerber, G.,
Valizadeh, S.,
Wright, J.,
Limbäck, M.,
Hallstadius, L.,
Gavillet, D.,
Abolhassani, S.,
Nagase, F.,
Sugiyama, T.,
Wiesenack, W.,
Tverberg, T.,
last modified
Aug 29, 2011 10:36 AM
2010 - In-core fuel performance and material characterization in the Halden Reactor
Van Nieuwenhove, R.,
Solstad, S.,
last modified
Mar 17, 2011 04:50 PM
